EN 62387-1:2012

SLOVENSKI STANDARD
01-maj-2012
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Radiation protection instrumentation - Passive integrating dosimetry systems for
environmental and personal monitoring - Part 1: General characteristics and
performance requirements
Strahlenschutz-Messgeräte - Passive, integrierende Dosimetriesysteme zur Umwelt- und
Personenüberwachung - Teil 1: Allgemeine Eigenschaften und Leistungsanforderungen
Instrumentation pour la radioprotection - Systèmes dosimétriques intégrés passifs pour
la surveillance de l'environnement et de l'individu - Partie 1: Caractéristiques générales
et exigences de fonctionnement
Ta slovenski standard je istoveten z: EN 62387-1:2012
ICS:
13.280 Varstvo pred sevanjem Radiation protection
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

EUROPEAN STANDARD
EN 62387-1
NORME EUROPÉENNE
February 2012
EUROPÄISCHE NORM
ICS 13.280
English version
Radiation protection instrumentation -
Passive integrating dosimetry systems for environmental and personal
monitoring -
Part 1: General characteristics and performance requirements
(IEC 62387-1:2007, modified)
Instrumentation pour la radioprotection -  Strahlenschutz-Messgeräte -
Systèmes dosimétriques intégrés passifs Passive, integrierende Dosimetriesysteme
pour la surveillance de l'environnement et zur Umwelt- und Personenüberwachung -
de l'individu - Teil 1: Allgemeine Eigenschaften und
Partie 1: Caractéristiques générales et Leistungsanforderungen
exigences de fonctionnement (IEC 62387-1:2007, modifiziert)
(CEI 62387-1:2007, modifiée)
This European Standard was approved by CENELEC on 2012-01-02. CENELEC members are bound to comply
with the CEN/CENELEC Internal Regulations which stipulate the conditions for giving this European Standard
the status of a national standard without any alteration.

Up-to-date lists and bibliographical references concerning such national standards may be obtained on
application to the CEN-CENELEC Management Centre or to any CENELEC member.

This European Standard exists in three official versions (English, French, German). A version in any other
language made by translation under the responsibility of a CENELEC member into its own language and notified
to the CEN-CENELEC Management Centre has the same status as the official versions.

CENELEC members are the national electrotechnical committees of Austria, Belgium, Bulgaria, Croatia, Cyprus,
the Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy,
Latvia, Lithuania, Luxembourg, Malta, the Netherlands, Norway, Poland, Portugal, Romania, Slovakia, Slovenia,
Spain, Sweden, Switzerland, Turkey and the United Kingdom.

CENELEC
European Committee for Electrotechnical Standardization
Comité Européen de Normalisation Electrotechnique
Europäisches Komitee für Elektrotechnische Normung

Management Centre: Avenue Marnix 17, B - 1000 Brussels

© 2012 CENELEC - All rights of exploitation in any form and by any means reserved worldwide for CENELEC members.
Ref. No. EN 62387-1:2012 E
Contents
For e wor d . 5
Introduction . 6
1 Scope and object . 7
2 Normative references . 8
3 Terms and definitions . 8
4 Units and symbols . 16
5 General test procedures . 16
5.1 Basic test procedures . 16
5.2 Test procedures to be considered for every test . 17
6 Performance requirements: summary . 18
7 Capability of a dosimetry system . 18
7.1 General . 18
7.2 Measuring range and type of radiation . 18
7.3 Rated ranges of the influence quantities . 18
7.4 Maximum rated measurement time t . 18
max
7.5 Reus abilit y . 18
7.6 Model function . 18
7.7 Example for the capabilities of a dosimetry system . 19
8 Requirements for the design of the dosimetry system . 19
8.1 General . 19
8.2 Indication of the dose value (dosimetry system) . 19
8.3 Assignment of the dose value to the dosemeter (dosimetry system) . 20
8.4 Information given on the devices (reader and dosemeter) . 20
8.5 Retention and removal of radioactive contamination (dosemeter) . 20
8.6 Algorithm to evaluate the indicated value (dosimetry system). 20
8.7 Use of dosemeters in mixed radiation fields (dosimetry system) . 20
9 Instruction manual. 21
9.1 General . 21
9.2 Specification of the technical data . 21
10 Software, data and interfaces of the dosimetry system . 22
10.1 General . 22
10.2 Requirements . 22
10.3 Method of test . 25
11 Radiation performance requirements and tests (dosimetry system) . 27
11.1 General . 27
11.2 Coefficient of variation . 27
11.3 Non-linearity . 28
11.4 Overload characteristics, after-effects, and reusability . 29
11.5 Radiation energy and angle of incidence for H (10) or H*(10) dosemeters . 30
p
11.6 Radiation energy and angle of incidence for H (0,07) dosemeters . 32
p
11.7 Over response to radiation incidence from the side of an H (10) or H (0,07)
p p
dosemeter . 34
11.8 Indication of the presence of beta dose for H (0,07) whole body dosemeters . 35
p
12 Response to mixed irradiations (dosimetry system) . 35
12.1 Requirements . 35
12.2 Method of test . 35

– 3 – EN 62387-1:2012
12.3 Interpretation of the results . 36
13 Environmental performance requirements and tests . 37
13.1 General . 37
13.2 Ambient temperature and relative humidity (dosemeter) . 37
13.3 Light exposure (dosemeter) . 38
13.4 Dose build-up, fading, self-irradiation, and response to natural radiation
(dosemeter) . 39
13.5 Sealing (dosemeter) . 40
13.6 Reader stability (reader) . 40
13.7 Ambient temperature (reader) . 41
13.8 Light exposure (reader) . 41
13.9 Primary power supply (reader) . 42
14 Electromagnetic performance requirements and tests (dosimetry system) . 43
14.1 General . 43
14.2 Requirement . 43
14.3 Method of test . 44
14.4 Interpretation of the results . 44
15 Mechanical performance requirements and tests . 44
15.1 General requirement . 44
15.2 Drop (dosemeter) . 45
16 Doc um ent a t io n . 45
16.1 Type test report . 45
16.2 Certificate issued by the laboratory performing the type test . 45
Annex A (normative) Confidence limits . 55
A.1 General . 55
A.2 Confidence interval for the mean, x . 56
A.3 Confidence interval for a combined quantity . 56
Annex B (informative) Causal connection between readout signals, indicated value and
measured value . 58
Annex C (informative) Overview of the necessary actions that have to be performed for a
type test according to this standard . 59
Annex D (informative) Usage categories of passive dosemeters . 61
Annex ZA (normative) Normative references to international publications with their
corresponding European publications . 62
Annex ZB (informative) Uncertainty of dosimetry systems . 64
Annex ZC (informative) Conversion coefficients h (0.07;S,α) and h (0.07;R,α) from air
pK pK
kerma, K , to the dose equivalent H (0.07) for radiation qualities defined in ISO 4037-1 and
a p
the rod, pillar and slab phantom . 65
Annex ZD (informative) Computational method of test for mixed irradiations. 66
Bibliography . 68
Figures
Figure A.1 – Test for confidence interval . 55
Figure B.1 – Data evaluation in dosimetry systems . 58
Figure ZD.1 – Flow chart of a computer program to perform tests according to 12.2 . 67

Tables
Table 1 – Symbols . 47
Table 2 – Reference conditions and standard test conditions . 49
Table 3 – Performance requirements for H (10) dosemeters . 50
p
Table 4 – Performance requirements for H (0,07) dosemeters . 51
p
Table 5 – Performance requirements for H*(10) dosemeters . 52
Table 6 – Environmental performance requirements for dosemeters and readers . 53
Table 7 – Electromagnetic disturbance performance requirements for dosimetry systems
according to Clause 14 . 54
Table 8 – Mechanical disturbances performance requirements for dosemeters . 54
Table A.1 – Student’s t-value for a double sided 95 % confidence interval . 56
Table C.1 – Schedule for a type test of a dosemeter for H (10) fulfilling the requirements
p
within the mandatory ranges . 59
Table D.1 – Usage categories of passive dosemeters . 61
Table ZC.1 – Conversion coefficients h (0,07;S,α) and h (0,07;R,α) from air kerma, K , to
pK pK a
the dose equivalent H (0.07) for radiation qualities defined in ISO 4037-1 and for the rod,
p
pillar, and slab phantom . 65

– 5 – EN 62387-1:2012
Foreword
This document (EN 62387-1:2012) consists of the text of IEC 62387-1:2007 prepared by
IEC/SC 45B, "Radiation protection instrumentation", of IEC/TC 45, "Nuclear instrumentation",
together with the common modifications prepared by CLC/TC 45B, "Radiation protection
instrumentation".
The following dates are fixed:

(dop) 2013-01-02
• latest date by which this document has to be
implemented
at national level by publication of an identical
national standard or by endorsement
(dow) 2015-01-02
• latest date by which the national standards conflicting
with this document have to be withdrawn
Attention is drawn to the possibility that some of the elements of this document may be the subject
of patent rights. CENELEC [and/or CEN] shall not be held responsible for identifying any or all such
patent rights.
Clauses, subclauses, notes, tables, figures and annexes which are additional to those in
IEC 62387-1:2007 are prefixed “Z”.

In this document, the common modifications to IEC 62387-1:2007 are indicated by a vertical line in
the left margin of the text.
The main objectives of EN 62387-1 are to
• specify performance requirements for complete dosimetry systems including detectors,
dosemeters, readers, and additional equipment. In addition, the corresponding methods of test
to check that these requirements are met are given in detail,
• harmonize requirements for all types of passive dosimetry systems detecting external photon
and beta radiation,
• specify the use the operational quantities according to ICRU 51,
• harmonize tests using radiation with relevant ISO standards on reference radiation and
calibration: ISO 4037 for photon radiation, ISO 6980 for beta radiation and ISO 8529 for neutron
radiation. For this reason, no conversion coefficients from air kerma (or absorbed dose or
fluence) to the operational quantities are given in this standard, except in case the necessary
conversion coefficients are not included in the respective ISO standard. Those given in the ISO-
standards are applicable,
• incorporate basic terms of the concept that a result of a measurement essentially consists of a
value and an associated uncertainty, as laid down in the introductions of IEV 311 and EN 60359
and refer the reader to an IEC technical report for complete uncertainty analysis in radiation
protection measurements and to the GUM,
• align CENELEC performance requirements on dosimetry systems for measuring personal dose
equivalents with the recommendations on accuracy stated in the ICRP Publication 75: General
Principles for the Radiation Protection of Workers. Further information is given in the informative
Annex ZB.
Introduction
A dosimetry system may consist of the following elements:
a) a passive device, referred to here as a detector, which, after the presence of radiation, provides
and stores a signal for use in measuring one or more quantities of the incident radiation field;
b) a dosemeter, that incorporates some means of identification and contains one or more
detectors;
c) a reader which is used to readout the stored information (signal) from the detector, in order to
determine the radiation dose;
d) a computer with appropriate software to control the reader, store the signals transmitted from
the reader, calculate, display and store the evaluated dose in the form of an electronic file or
paper copy;
e) additional equipment and documented procedures (instruction manual) for performing
associated processes such as deleting stored dose information, cleaning dosemeters, or those
needed to ensure the effectiveness of the whole system.

– 7 – EN 62387-1:2012
1 Scope and object
This European Standard applies to all kinds of passive dosimetry systems that are used for
measuring
– the personal dose equivalent H (10) (for whole body dosimetry),
p
– the personal dose equivalent H (0,07) (for both whole body and extremity dosimetry),or
p
– the ambient dose equivalent H*(10) (for environmental dosimetry).
It applies to dosimetry systems that measure external photon or beta radiation in the dose range
between 0,01 mSv and 10 Sv and in the energy ranges given in the following Table. All the energy
values are mean energies with respect to the prevailing dose quantity. The dosimetry systems
usually use electronic devices for the data evaluation and thus are often computer controlled.
Mandatory energy Maximum energy Mandatory energy Maximum energy range for
Measuring
range for photon range for testing range for beta- testing beta-particle
quantity
radiation
photon radiation particle radiation radiation
H (10),
p
80 keV to 1,25 MeV 12 keV to 7 MeV --- ---
H*(10)
0,8 MeV
a
0,07 MeV to 1,2 MeV
almost equivalent
H(0,07) 30 keV to 250 keV 8 keV to 7 MeV almost equivalent to E
p max
to an E of
max
from 0,225 MeV to 3,54 MeV
2,27 MeV
a
For beta-particle radiation, an energy of 0,07 MeV is required to penetrate the dead layer of skin of 0,07 mm
(almost equivalent to 0,07 mm of ICRU tissue).

NOTE 1  In this standard, “dose” means personal or ambient dose equivalent, unless otherwise stated.
NOTE 2  For H (10) and H*(10) no beta radiation is considered. Reasons: 1) H (10) and H*(10) are a conservative
p p
estimate for the effective dose which is not a suitable quantity for beta radiation. 2) No conversion coefficients are
available in ICRU 56, ICRU 57 or ISO 6980.
NOTE 3  The maximum energy ranges are the energy limits within which type tests according to this standard are
possible.
In addition, this standard can be applied for testing neutron dosimetry systems concerning the
design (Clause 8), the instruction manual (Clause 9), the software (Clause 10), environmental
influences (Clause 13), electromagnetic influences (Clause 14), mechanical influences (Clause 15),
and the documentation (Clause 16). The test utilizing radiation (Clauses 13 to 15) shall be done
with neutron reference radiation qualities according to the ISO 8529 series.
In some countries the presence of beta dose has to be indicated by dosemeters worn on the trunk.
Such an indication of the presence of beta dose is not a measurement. For that reason, a specific
subclause (11.8) deals with the indication of the presence of beta dose.
This standard is intended to be applied to dosimetry systems that are capable of evaluating doses
in the required quantity and unit (Sv) from readout signals in any quantity and unit. The only
correction that may be applied to the evaluated dose (indicated value) is the one resulting from
natural background radiation using extra dosemeters.
NOTE 4  The correction due to natural background may be made before or after the dose calculation.
Usually, a dosimetry system is not able to measure all quantities given above. Thus, the systems
shall only be tested with regards to those quantities and types of radiation it is intended to be used
for. Annex D gives further guidelines to define specific usage categories.
Full compliance with this standard is given if the requirements for the mandatory ranges given in
Tables 3 to 5 are fulfilled. If the customer or manufacturer requires extended ranges then the test
should also be performed as specified in this standard, i.e. the requirements given in Tables 3 to 5
apply, too. The range of any influence quantity stated by the manufacturer is called rated range.
Thus, dosimetry systems can be classified by stating a set of ranges (for example, for dose, for
energy, for temperature) within which the requirements stated in this standard are met (Capabilities
of the system, see Clause 7). In addition, usage categories are given in Annex D with respect to
different measuring capabilities.

For the dosimetry systems described above, this standard specifies general characteristics, general
test procedures and performance requirements, radiation characteristics as well as environmental,
electrical, mechanical, software and safety characteristics.
A dosimetry system may be tested with regards to different quantities at different times. In case the
dosimetry system was changed since the previous test, a new test with regards to quantities tests
formerly may be necessary.
The absolute calibration of the dosimetry system is not checked during a type test according to this
standard as only system properties are of interest. The absolute calibration is checked during a
routine test.
2 Normative references
For normative references, see the normative Annex ZA.
3 Terms and definitions
For the purposes of this document, the following terms and definitions apply.
For definitions related to measurements in general, definitions were taken from
IEC 60050-300, Part 311, from IEC 60050-393 and from IEC 60050-394. A very limited number of
definitions was taken from ISO 4037-3 and the ISO Guide to the Expression of Uncertainty in
Measurement (GUM).
The references are given in brackets [ ]. The information following the brackets is specific to this
standard and is not originating from the given source.
A word between parentheses ( ) in the title of a definition is a qualifier that may be skipped if there
is no danger of confusion with a similar term.
The terms are listed in alphabetical order.
3.1
ambient dose equivalent
H*(d)
at a point in a radiation field, dose equivalent that would be produced by the corresponding
expanded and aligned field, in the ICRU sphere at a depth, d, on the radius opposing the direction
of the aligned field
[SOURCE: ICRU 51]
Note 1 to entry: The recommended depth, d, for environmental monitoring in terms of H*(d) is 10 mm, and H*(d) may be
written as H*(10). [IEV 393-14-95]
3.2
calibration factor
N
quotient of the conventional true value of a quantity C and the indicated value G at the point of
r,0 r,0
test for a reference radiation under reference conditions. It is expressed as
C
r,0
N =
G
r,0
Note 1 to entry: The reciprocal of the calibration factor is equal to the response under reference conditions. In contrast to
the calibration factor, which refers to the reference conditions only, the response refers to any conditions prevailing at the
time of measurement.
[SOURCE: ISO 4037-3, Definition 3.2.12, modified]
Note 2 to entry: This definition is of special importance for non-linear dosemeters.
Note 3 to entry: The reference value C for the dose is given in Table 2.
r,0
– 9 – EN 62387-1:2012
3.3
coefficient of variation
v
ratio of the standard deviation s to the arithmetic mean G of a set of n indicated values G
j
(indicated value) given by the following formula:
n
s 1 1 2
v = = ()G − G
∑ j
n −1
G G
j=1
[SOURCE: IEV 394-20-14, modified]
3.4
conventional true value (of a quantity)
C
value attributed to a particular quantity and accepted, sometimes by convention, as having an
uncertainty appropriate for a given purpose
Note 1 to entry: "Conventional true value" is sometimes called “assigned value”, “best estimate of the value”,
“conventional value” or “reference value”.
[SOURCE: GUM B.2.4]
3.5
correction for non-linearity
r
n
quotient of the response R under conditions where only the value of the dose equivalent is varied,
n
and the reference response R . It is expressed as
R
n
r =
n
R
Note 1 to entry: For a linear dosimetry system, r is equal to unity.
n
3.6
coverage factor
k
numerical factor used as a multiplier of the combined standard uncertainty in order to obtain an
expanded uncertainty
Note 1 to entry: A coverage factor k is typically in the range 2 to 3.
[SOURCE: GUM 2.3.6]
Note 2 to entry: In case of a normal distribution, using a coverage factor of 2 results in an expanded uncertainty that
defines an interval around the result of a measurement that contains approximately 95 % of the distribution of values that
could reasonably be attributed to the measurand. For other distributions, the coverage factor may be larger.
3.7
detector
element of equipment or a substance which, in the presence of radiation, provides a signal for use
in measuring one or more quantities of the incident radiation

[SOURCE: IEV 394-04-01]
Note 1 to entry: The detector usually requires a separate reader to read out the signal. That means the detector usually is
not able to provide a signal without any external reading process.
Note 2 to entry: A passive detector does not need an external power supply to collect and store dose information.
Note 3 to entry: In IEV, the term reads “radiation detector”.

3.8
deviation
D
difference between the indicated values for the same value of the measurand of a dosimetry
system, when an influence quantity assumes, successively, two different values
[SOURCE: IEV 311-07-03, modified]
D = G – G
r
where
G the indicated value under the effect; and
G the indicated value under reference conditions.
r
Note 1 to entry: The original term in IEV 311-07-03 reads “variation (due to an influence quantity)”. In order not to mix up
variation (of the indicated value) and variation of the response, in this standard, the term is called “deviation”.
Note 2 to entry: The deviation can be positive or negative resulting in an increase or a decrease of the indicated value,
respectively.
3.9
dosemeter
radiation meter designed to measure the quantities absorbed dose or dose equivalent
Note 1 to entry: In a wider sense, this term is used for meters designed to measure other quantities related to radiation
such as exposure, fluence, etc. Such use is deprecated.
Note 2 to entry: This apparatus may require a separate reader to read out the absorbed dose or dose equivalent.
[SOURCE: IEV 394-02-11]
Note 3 to entry: A dosemeter usually consists of a detector and a badge, for example TLD badge with filters.
3.10
dosimetry system
dosemeter, reader and all associated equipment and procedures used for assessing the indicated
value
[SOURCE: IEV 394-11-06, modified]
3.11
expanded uncertainty
U
quantity defining an interval about the result of a measurement that may be expected to encompass
a large fraction of the distribution of values that could reasonably be attributed to the measurand
[SOURCE: GUM 2.3.5]
Note 1 to entry: The expanded uncertainty is obtained by multiplying the combined standard uncertainty by a coverage
factor.
Note 2 to entry: A confidence level of 95 % is recommended for the use of this standard.
3.12
indicated value
G
value of the measurand given directly by a measuring instrument on the basis of its calibration
curve
[SOURCE: IEV 311-01-08]
Note 1 to entry: In this standard, the indicated value is the one given by the dosimetry systems as the final result of the
evaluation algorithm (for example, display of the software, print out) in units of dose equivalent (Sv), see 8.2.
Note 2 to entry: The indicated value is equivalent to the evaluated value in ISO 12794, Annex D.

– 11 – EN 62387-1:2012
Note 3 to entry: For details, see Annex B of this standard.
3.13
influence quantity
quantity that is not the measurand but that affects the result of the measurement
Note 1 to entry: For example, temperature of a micrometer used to measure length.
[SOURCE: IEV 394-20-27; GUM B.2.10]
Note 2 to entry: If the effect on the result of a measurement of an influence quantity depends on another influence
quantity, these influence quantities are treated as a single one. In this standard, this is the case for two pairs of influence
quantities:
1 – radiation energy and angle of incidence,
2 – ambient temperature and relative humidity.
3.14
influence quantity of type F
influence quantity whose effect on the indicated value is a change in response
Note 1 to entry: An example is radiation energy and angle of radiation incidence.
Note 2 to entry: F stands for factor. The indication due to radiation is multiplied by a factor due to the influence quantity.
3.15
influence quantity of type S
influence quantity whose effect on the indicated value is a deviation independent of the indicated
value
Note 1 to entry: An example is the electromagnetic disturbance.
Note 2 to entry: All requirements for influence quantities of type S are given with respect to the value of the deviation D.
Note 3 to entry: S stands for sum. The indication is the sum of the indication due to radiation and due to the disturbance.
3.16
lower limit of the measuring range
H
low
lowest dose value included in the measuring range
3.17
maximum rated measurement time
t
max
longest continuous period of time over which the dose is accumulated and over which all
requirements of this standard are fulfilled
Note 1 to entry: The maximum rated measuring time depends on the lower limit of the measuring range H , the fading,
low
and other influences.
Note 2 to entry: The beginning of this period of time can for example be erasing the dose by heating (at TLDs) or a dose
reset by means of software (at DIS).
3.18
measured value
M
value that can be obtained from the indicated value G by applying the model function for the
measurement
Note 1 to entry: The uncertainty model function combines the indicated value G with the reference calibration factor N ,
the correction for non-linearity r , the l deviations D (p = 1.l) for the influence quantities of type S, and the m relative
n p
response values r (q = 1.m) for the influence quantities of type F:
q
 l 
N
 
M = G − D .
∑ p
m
 
p=1
 
r r
n ∏ q
q=1
This uncertainty model function is necessary to evaluate the uncertainty of the measured value according to the GUM (see
GUM, 3.1.6, 3.4.1 and 4.1).
Note 2 to entry: For “model” function, see Note 2 to 3.35.
Note 3 to entry: The calculations according to this model function are usually not performed, only in the case that specific
influence quantities are well known and an appropriate correction is applied.
Note 4 to entry: If necessary, another model function closer to the design of a certain dosimetry system may be used.
Note 5 to entry: For details, see Annex B.
3.19
measuring range
range defined by two values of the measurand, or quantity to be supplied, within which the limits of
uncertainty of the measuring instrument are specified
[SOURCE: IEV 311-03-12]
Note 1 to entry: In this standard, the measuring range is the range of dose equivalent, in which the requirements of this
standard are fulfilled and thus the uncertainty is limited.
3.20
mandatory range (of use)
smallest range being specified for an influence quantity or instrument parameter over which the
dosimetry system shall operate in compliance with this standard
Note 1 to entry: The mandatory ranges of the influence quantities dealt with in this standard are given in the second
column of Tables 3 to 7.
3.21
personal dose equivalent
H (d)
p
dose equivalent in soft tissue, at an appropriate depth, d, below a specified point on the body
[SOURCE: ICRU 51]
Note 1 to entry: The recommended depths are 10 mm for penetrating radiation and 0,07 mm for superficial radiation.
[IEV 393-14-97]
Note 2 to entry: Soft tissue means ICRU 4-element tissue, see ICRU Report 39.
3.22
point of test
point in the radiation field at which the conventional true value of the quantity to be measured is
known
[SOURCE: ISO 4037-3, Definition 3.2.6, modified]
3.23
preparation
normal treatment of dosemeters or detectors before a dose measurement, for example, a procedure
to erase stored dose information, reset the dose information by means of software, cleaning, which
the dosemeters or detectors are intended to be subjected to in routine use
3.24
rated range (of use)
specified range of values which an influence quantity can assume without causing a deviation or
variation of the response exceeding specified limits
[SOURCE: IEV 311-07-05, modified]

– 13 – EN 62387-1:2012
Note 1 to entry: In IEV 311-07-05, the term reads “nominal range of use”. In this standard, “rated range” is used in order
to avoid complicated terms like “the range of use of an influence quantity” but to have terms that are easily readable like
“the rated range of an influence quantity”.
Note 2 to entry: Influence quantities can be either of type S or of type F.
3.25
reader
instrument designed to read out one or more detectors in a dosemeter
[SOURCE: IEV 394-11-10, modified]
Note 1 to entry: Signal of a passive dosimeter can be amount of light, amount of charge, transparency of film and so on.
Each type of passive dosimeter thus has very a different type of reader.
Note 2 to entry: In IEV, the term reads “dosemeter reader”.
3.26
readout
process of measuring the stored dose information of a detector in a reader
3.27
reference conditions
set of specified values and/or ranges of values of influence quantities under which the uncertainties
admissible for a dosimetry system are the smallest
[SOURCE: IEV 311-06-02, modified]
3.28
reference direction
direction, in the coordinate system of a dosemeter, with respect to which the angle to the direction
of radiation incidence is measured in unidirectional fields
[SOURCE: ISO 4037-3, 3.2.7]
3.29
reference orientation
(dosemeter) orientation for which the direction of the incident radiation coincides with the reference
direction of the dosemeter
[SOURCE: ISO 4037-3, 3.2.8]
3.30
reference point of a dosemeter
physical mark or marks on the outside of the dosemeter to be used in order to position it with
respect to the point of test
[SOURCE: IEV 394-20-15, modified]
3.31
reference response
R
response for a reference value C of the quantity to be measured under reference conditions
r,0
G
r,0
R =
C
r,0
where G is the corresponding indicated value
r,0
Note 1 to entry: The reference response is the reciprocal of the reference calibration factor.
Note 2 to entry: The reference values for the dose are given in Table 2.

3.32
relative expanded uncertainty
U
rel
expanded uncertainty divided by the measurement result
3.33
relative response
r
quotient of the response R and the reference response R
R
r =
R
3.34
response (of a radiation measuring assembly)
R
ratio, under specified conditions, given by the relation:
G
R =
C
where
G is the indicated value of the quantity measured by the equipment or assembly under test
(dosimetry system); and
C is the conventional true value of this quantity.
[SOURCE: IEV 394-20-21, modified]
Note 1 to entry: The value of the response may vary with the dose being measured. In such cases, a dosimetry system is
said to be non-linear.
3.35
result of a measurement
set of values attributed to a measurand, including a value, the corresponding uncertainty, and the
unit of the measurand
Note 1 to entry: The central value of the whole (set of values) can be selected as measured value M (see 3.18) and a
parameter characterizing the dispersion as uncertainty (see 3.39).
Note 2 to entry: The result of a measurement is related to the indicated value given by the instrument G (see 3.12) and to
the values of correction obtained by calibration and by the use of a model (see 3.18).
[SOURCE: IEV 311-01-01, modified]
Note 3 to entry: The estimation of M can be based on one or more indicated values.
3.36
signal
S
quantity obtained in a reader after readout of a detector from which the indicated value of the dose
equivalent is evaluated
Note 1 to entry: Examples are the charge measured in a photomultiplier tube due to TL-light; the area of a certain region
from a glow curve of a TL detector; a fitting parameter evaluated from a glow curve analysis.
Note 2 to entry: In principle, it is possible to obtain more than one signal from one detector (for example several fitting
parameters from a glow curve analysis).
Note 3 to entry: Using more than one detector always means using more than one signal.
Note 4 to entry: The “signal” is similar to the “readout value” in ISO 12794:2000, 3.13.
Note 5 to entry: For details, see Annex B of this standard.

– 15 – EN 62387-1:2012
3.37
standard deviation
s
for a series of n measurements of the same measurand, the quantity s characterizing the dispersion
of the results and given by the formula:
n
s = ()G − G
j
∑
n −1
j=1
where
G is the result of the j-th measurement; and
j
G is the arithmetic mean of the n results considered.
Note 1 to entry: Considering the series of n values as sample of a distribution, G is an unbiased estimate of the mean µ,
2 2
and s is an unbiased estimate of the variance σ of that distribution.
Note 2 to entry: The expression s / n is an estimate of the standard deviation of the distribution of G and is called the
“experimental standard deviation of the mean”.
Note 3 to entry: Experimental standard deviation of the mean" is sometimes incorrectly called “standard error of the
mean”.
[SOURCE: IEV 394-20-44, modified]
Note 4 to entry: In IEV, the term reads “experimental standard deviation”.
3.38
standard test conditions
range of values of a set of influence quantities under which a calibration or a determination of
response is carried out
Note 1 to entry: Ideally, calibrations should be carried out under reference conditions. As this is not always achievable
(for example, for ambient air pressure) or convenient (for example, for ambient temperature), a (small) interval around the
reference values may be used. The deviation of the calibration factor from its value under reference conditions caused by
these deviations should in principle be corrected for.
Note 2 to entry: During type tests, all values of influence quantities which are not the subject of the test are fixed within
the interval of the standard test conditions.
[SOURCE: ISO 4037-3, Definition 3.2.3]
3.39
standard uncertainty
u
uncertainty of the result of a measurement expressed as a standard deviation
[SOURCE: GUM 2.3.1]
Note 1 to entry: Standard uncertainty is a more general term than standard deviation, for example, standard uncertainty
may also contain uncertainty contributions evaluated using non statistical methods.
3.40
type test
conformity testing on the basis of one or more specimens of a product representative of the
production
[SOURCE: IEV 394-20-28]
3.41
upper limit of the measuring range
H
up
highest dose value included in the measuring range

4 Units and symbols
In the present standard, units of the international system (SI) are used. Nevertheless, the following
units may be acceptable in common usage:
–19
– for energy: electron-volt (symbol eV). 1 eV = 1,602 × 10 J
– for time: year, month, day, hour (symbol h), minute (symbol min).
Multiples and submultiples of SI units may be used, according to the SI system.
–1
The SI unit of dose equivalent is 1 J kg .
–1
The special name for the unit of the dose equivalent is sievert (symbol Sv). 1 Sv = 1 J kg .
A list of symbols is given in Table 1 (at the end of the document).
5 General test procedures
5.1 Basic test procedures
5.1.1 Instructions for use
The instructions for use of the dosimetry systems have to be unambiguously given in the manual,
see Clause 9. These instructions have to be the same for all parts of the type test and for the
routine use as well.
5.1.2 Nature of tests
The tests listed in this standard are considered to be type tests, see Annex C.
5.1.3 Reference conditions and standard test conditions
Reference conditions are given in the second column of Table 2 (at the end of the document). The
tests shall be carried out under standard test conditions given in the third column of Table 2, unless
otherwise specified.
All influence quantities shall be maintained withi
...